NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl

Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl

ML20247B322
Person / Time
Site:	Browns Ferry
Issue date:	03/22/1989
From:	Gears G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
RTR-NUREG-1061 TAC-00016, TAC-16, NUDOCS 8903290354
Download: ML20247B322 (16)

Text

r: ~ _ _ _.-

- _--_---- ----- -------- ----~ ~~~'

k#  %

/ \,- . UNITED STATES -

NUCLEAR REGULATORY COMMISSION l 4 j j WASHINGTON, D. C. 20666 R- + , u . . lr March 22, 1989 Docket No. 50-260 LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant, Unit 2

SUMMARY

L0F FEBRUARY 17, 1989 MEETING.BETWEEN NRC AND-TVA l REGARDING SEISMIC ISSUES AT BROWNS FERRY (TAC NO. 00016).

the staff met with the Tennessee Valley Authority-(TVA On February)17, or licensee at the 1989, NRC Offices _in Rockville, Maryland to discuss resolution of open civil / seismic issues pertaining to the, Browns Ferry Nuclear Plant (BFN) Unit 2. Enclosure 1 contains a list of- the meeting participants. _ i Enclosure 2 contains TVA's. handouts used at the meeting. Detailed-documentation of the meeting is contained in a meeting transcript previously transmitted to TVA_by a letter dated February 23, 1989.

The majority of the open. items discussed at the meeting had been identified l during the recent staff, audit (January 23 - February 3,:1989) of the piping reanalysis effort. Although many issues were resolved during the audit, the '

staff and TVA had not agreed on the resolution of _ some. issues related to' design criteria. These issues were the basis for discussion at this meeting. The' ,

details'of the resolution of all the issues identified during the piping audit will be documented in an inspection report. i In the beginning of the meeting the staff expressed its concern that TVA had made little progress in correctiy pipe support design deficiencies at Browns j Ferry that had been identified by TVA aq early as January 1980. In addition,  !

-the staff expressed its concern that T,AV had made additional changes to the i piping and support design criteria as late as January 20, 1989. TVA started the meeting by summari::ing the agreements- for corrective actions that had '

been reached with the staff for resolution of some of the civil / seismic issues. These issues are listed in Item II of TVA's agenda. The majority of the meeting focused on open issues where agreement for corrective actions had not been reached. The following paragraphs sunenarize the staff's position on the open items discussed at the meeting:

a. Load Sharing / Spring Bottoming (EMG-12)

These issues involved TVA's restart criteria for piping and supports. )

The staff provided TVA its position on the restart criteria i (CEB-CI-21.97) in a March 1988 meeting on the Browns Ferry piping l program. During the recent audit of TVA's program, the staff reviewed j TVA's latest revision of the restart criteria (BFN-50-C-7303) and presented i TVA the same position on the criteria that it had provided in the March 1988 meeting. At the audit exit meeting, TVA had not agreed to the staff positions on load sharing or springs bottoming out. During this meeting, l 0

$$$2ggggggjgggo P

ug

1 2

TVA proposed to accept the staff position to correct bottomed-out spring hangers prior to restart. On the issue of load sharing, the staff stated its position that the load sharing provisions were not acceptable criteria for deferring modifications until the next Browns Ferry refueling outage. TVA agreed to delete the load sharing provisions from all applicable criteria documents,

b. Low Temperature Thermal Analysis (EMG-20) l This issue involved TVA's January 20, 1989 revision of the piping analysis design criteria (BFN-50-C-7103). The recent' revision had excluded the thermal analysis of piping systems with temperatures between 32*F and 150*F. The staff had questioned the basis for excluding this

. low temperature thermal analysis during the recent audit. In addition, this recent exclusion of the low temperature analysis appears to contradict the commitment for corrective action in Employee Concerns Subcategory Report No. 21800 that had been recently submitted to the staff (TVA letter - Gridley to NRC dated February 6 1989). At the meeting, TVA stated its position that detailed thermal analysis of low temperature piping systems would not be performed. The staff stated that it did not accept TVA's position because of the conflict with the Employee Concerns Program corrective action comitment.

c. Use of Clay Pipe Material (EMG-019)

During the audit of the piping reanalysis effort, TVA found that the EECW system discharged through a non-safety-related portion of the raw cooling water system which contained vitrified clay pipe. At the meeting, TVA stated it had not determined the long-term corrective action for the EECW discharge piping. This item remains open until TVA defines its corrective action.

d. Control Rod Drive HydrauH e System (EMG-027)

During the audit of the piping reanalysis effort, TVA stated that the design criteria for the control rod drive hydraulic system had not been finalized. During the meeting TVA stated that it was performing a study to justify using an SRSS methodology for combining loads from individual pipe run and that the study was not complete. The staff stated that it would review TVA's proposed criteria when the study is complete and the criteria have been finalized.

e. Rod Hangers (EMC-006)

TVA proposed in the pipe support design criteria to use rod hangers, on a case-by-case basis, to support compressive. loads. During the audit of the piping reanalysis effort, the staff had stated that the rod hangers should be modified to function as a pipe strut in order to use the rod hanger as a compression member. The basis for the staff position was that pipe support hanger manufacturers do not recomend using rod l

l

~

3 I

hangers in compression and that standard industry practice is to use pipe struts for compression forces. At the meeting, the staff reaffirmed its position that the rod hangers should be modified to function as typical pipe support compression members if TVA uses the rod hanger to resist compressive forces.

f. Criteria for Drywell Platform Clip Angles (CSG-19)

This issue had been identified during an audit of TVA's civil program.

TVA had originally proposed a set of restart criteria for allowable stresses that the staff had accepted. During the audit, the staff identified that a revision of the criteria added a provision for using test data to qualify the clip angles, At the meeting, TVA decided that since only 13 clip angles were involved it was not worth the effort to justify the applicability of the test data. Therefore, TVA would use the restart criteria that had been previously approved by the staff.

g. SRSS of Inertia and Seismic Anchor Movement Loads (EMG-002)

During the staff audit of the piping analysis program, the staff identified that TVA's new revisions of the piping and pipe support design criteria documents had relaxed the criteria for the combination of seismic inertia and anchor movements from the previous revision of the criteria documents. The basis for this relaxation provided by TVA at the audit was a staff position contained in NUREG-1061. A^ the audit, the staff stated that it would check the NRC's staff implementation of this position and would provide TVA a position on this issue. At the meeting, the staff stated that the SRSS of inertia and anchor motions for independent support motion was acceptable if implemented according to the position in NUREG-1061. However, the staff also stated that Section 6.3(b)(2) of BFN-50-C-7103 did not appear to be in compliance with the position. That item involved the SRSS of the three separate direction load cases evaluated for the branch line connection. The basis for the staff concern was that for a branch line connection the three directional movements are not necessarily statistically independent and, therefore, SRSS would not be appropriate. The staff further stated that the use of absolute sum would be an acceptable approach for the branch line movements.

' A A.

, '&G er ld E. Gears Project Manager T Projects Division Office of Nuclear Reactor Regulation

Enclosures:

1. Attendance List

2. Slides Presented by TVA cc w/ enclosures:

See next page

hangers in compr:ssion and that standard industry practice is to us2 pipe struts for compression forces. At the meeting, the staff reaffirmed its position that the rod hangers should be modified to function as typical pipe support compression members if TVA uses the rod hanger to resist compressive forces.

f. Criteria for Drywell Platform Clip Angles (CSG-19)

This issue had been identified during an audit of TVA's civil program.

TVA had originally proposed a set of restart criteria for allowable stresses that the staff had accepted. During the audit, the staff identified that a revision of the criteria added a provision for using test data to qualify the clip angles. At the meeting, TVA decided that since only 13 clip angles were involved it was not worth the effort to justify the applicability of the test data. Therefore, TVA would use the restart criteria that had been previously approved by the staff.

g. SRSS of Inertia and Seismic Anchor Movement Loads (EMG-002)

During the staff audit of the piping analysis program, the staff identified that TVA's new revisions of the piping and pipe support design criteria documents had relaxed the criteria for the combination of seismic inertia and anchor movements from the previous revision of the criteria documents. The basis for this relaxation provided by TVA at the audit was a staff position contained in NUREG-1061. At the audit, the staff stated that it would check the NRC's staff implementation of this position and would provide TVA a position on this issue. At the meeting, the staff stated that the SRSS of inertia and anchor motions for independent support motion was acceptable if implemented according to the position in NUREG-1061. However, the staff also stated that Section 6.3(b)(2) of BFN-50-C-7103 did not appear to be in compliance with the position. That item involved the SRSS of the three separate direction load cases evaluated for the branch line connection. The basis for the staff concern was that for a branch line connection the three directional movements are not necessarily statistically independent and, therefore, SRSS would not be appropriate. The staff further stated that the use of absolute sum would be an acceptable approach for the branch line movements.

Original signed by Gerald E. Gears, Project Manager l

1 TVA Projects Division Office of Nuclear Reactor Regulation l

Enclosures:

1. Attendance List

2. Slides Presented by TVA cc w/ enclosures:

See next page Distribution l Docket File l NRC PDR Local PDR Those on Attached List OFC :NRR:TVA/LA :NRR:TVA/PM :NRR:TVA/BC :TVA- P :TVA:AD/P :T..  :

.:____. _ .. : - _ _4 N ..:_________ .

NAME :MSimms :GGe f'W:DTerao p:RPier :SBlac :BDLi w  :

!bb/ h :bb/Ubh :b3fE)bh :bbfI[fbh :bkhbh  !

bATb!b5)Mfb9 1 MWWL_________._.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

\

(

Browns Ferry Nuclear Plant cc:

General Counsel Regional Administrator, Region II Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive 101 Marietta Street, N.W.

E11 B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector / Browns Ferry NP Mr. R. L.'Gridley U.S. Nuclear Regulatory Commission Tennessee Valley Authority Route 12, Box 637 SN 157B Lookout Place Athens, Alabama 35611 Chattanooga, Tennessee 37402-2801 Mr. C. Mason Dr. Henry Myers, Science Advisor Tennessee Valley Authority Committee on Interior Browns Ferry Nuclear Plant and Insular Affairs P.O. Box 2000 U. S. House of Representatives Decatur, Alabama 35602 Washington, D.C. 20515 Tennessee Valley Authority Mr. P. Carier . .

Rockville Office Tennessee Valley Authority 11921 Rockville Pike Browns Ferry Nuclear Plant Suite 402 P.O. Box 2000 Rockville, Maryland 20852 Decatur, Alabama 35602 Mr. Oliver D. Kings 1cy, Jr.

Mr. D. L. Williams Senior Vice President, Nuclear Power Tennessee Valley Authority Tennessee Valley Authority 400 West Summit Hill. Drive 6N 38A Lookout Place W10 B85 1101 Market Street Knoxville, Tennessee 37902 Chattanooga, Tennessee 37402-2801 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Claude Earl Fox, M.D.

State Health Officer State Department of Public Health State Office Building Mnntgomery, Alabama 36130 i

i

_a_m--._m_m___ __

[.

l .

ENCLOSURE 1 ATTENDANCE LIST FEBRUARY 17, 1989 MEETING Name Affiliation Wayne A..Massie TVA Gerry Gears NRC W..S. Raughley TVA E J. K. McCall TVA l F. L. Moreadith TVA C. H. Fox TVA P. Carier TVA L R. Pierson NRC l D. Terao. NRC B. D. Liaw NRC i J. R. Fair NRC l T. M. Cheng NRC l E. F. Goodwin NRC R. Haupt TVA Alan Chan TVA

__--_-_---____.________n_-. _ _ _ . - - - _ - _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ . - _ _ . _ - _ - _ - _ _ _ _ _ . - _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - . _ _ _ _ . _ . - - _ _ . - _ _ _ - - . . . - - _ . _ _ _ _ _ _ . _ _ - - . _ _ - - - - - - _ _ _ _ _

ENCLOSURE 2 TVA / NRC MEETING FEBRUARY 17, 1989 R0CKVILLE, MD BROWNS FERRY NUCLEAR PLANT UNIT 2 NPK-h226M

,r,.*

~

BFN CIVIL ISSUE Cl0SURE MEETING FEBRUARY 17, 1989 l '. INTRODUCTION

.II .

SUMMARY

'0F ITEMS CLOSED CSG 9, 14, 24, 26 EMG 1, 2, 5, 13 III. OPFN TECHNICAL ISSUES.

A. LOAD SHARING / SPRING BOTTOMING- (EMG 12)

B. LOW. TEMPERATURE THERMAL ANALYSIS (EMG 20) c.- 'CRDH- (EMG 27)

D. CLAY PIPE (EMG 19)-

IV. ITEMS FOR FURTHER DISCUSSION A. ROD HANGERS (EMG 6)

B. DRYWELL PLATFORM CLIP ANGLES (CSG 19)

-V. WRAP UP

SUMMARY

NPK-4226M

,. u 4

LOAD SHARING ('EMG-012)

(REDISTRIBUTION OF FORCES)

STATEMENT OF THE ISSUE

' o LOAD SHARING-IS'PART OF INTERIM OPERABILITY CRITERIA o BFN METHODOLOGY SAME AS APPROVED AT SQNP

, PROPOSED RESOLUTION-

'o: APPLICABLE TO APPR0XIMATELY 200 SUPPORTS OUT OF "APPR0XIMATELY 3500 SUPPORTS o TWO RIG 0ROUS' ANALYSES (ARS) TO BE PERFORMED FOR EACH CASE

- SUPPORTS ACTIVE

- SUPPORT INACTIVE

• 0' o ADJACENT SUPPORTS QUALIFIED TO MAXIMUM ENVELOPED SUPPORT LOADS 4226M L

l i

9 SPRING HANGER EDTTOMING (EMG-012)

STATEMENT OF THE ISSUE e ACCEPTABILITY OF BOTTOMED-0UT SPRING CONDITION PROPOSED RESOLUTION

• BOTTOMED-0UT. SPRING CONDITIONS WILL BE CORRECTED FOR RESTART (WHICH IS SAME AS SQN)

• IMPACT: OUT OF 400 TOTAL SPRINGS, AN ESTIMATED 55 WILL BE RESET AND 21 WILL BE MODIFIED NPK3 - 189IIF

m -_

.f

.p . i f c

a:- wjy

-LOW-TEMPERATURE THERMAL. ANALYSIS (EMG-020)

STATE OF'THE ISSUE

• - EXCLUSION.OF. LOW TEMPERATURE (320 TO 1500F) PIPING THERMAL ANALYSIS 4 t

2

PROPOSED RES0t_UTION~

• - $XCLUSION 0F. LOW TEMPERATURE PIPING THERMAL:

ANALYSIS IS= ACCEPTABLE AND IS CONSISTENT WITH INDUSTRY PRACTICE-I l

l l

NPK3-1902F

p . m..

CONTROL ROD DRIVE HYDRAULIC SYSTEM (EMG-027)

STATEMENT OF THE-ISSUE

• DESIGN CRITERIA'FOR THE CRDH PIPING SYSTEM PROPOSFD RESOLUTION

• SEISMIC CLASS I CRITERIA.(BFN-50-C-7103 AND 7107)

WILL APPLY TO THE CRDH SYSTEM q

• GANG HANGERS WILL BE QUALIFIED BY COMBINING INDIVIDUAL SEISMIC PIPING FORCES BY'SRSS

• COMPLETED 800 MODS, ALL 3000 CLAMPS REPLACED l

NPK3-1901P l

L_ -- _ -- ___ .

g.

f

'USE 0F CLAY PIPE MATERIAL (EMG-019)

STATEMENT OF THE ISSUE e' TVA HAS ADVISED NRC 0F-USAGE OF CLAY PIPE IN.THE RAW

' COOLING WATER DISCHARGE PIPING. PORTIONS OF THE EMERGENCY EQUIPMENT COOLING WATER SYSTEM DISCHARGE INTO THIS RCW PIPING PROPOSED RES01UTION

• INTERIM OPERABILITY HAS BEEN ASSURED

• LONG TERM RESOLUTION IN PROGRESS l'

NPK-4226M

J ROD:HANGERSL(EMG-006T r

~

. STATEMENT 0F THE ISSUE

.* USE[0FR0DHANGERSIN_ COMPRESSION q, EROPOSED RESOLUTION'

• FOR' NET UPWARD. LOAD CONDITION, TVA WILL QUALIFY.

, EXISTING SUPP0PT CONFIGURATION.0R MODIFY. SUPPORT-

• ESTIMATE:300 OUT OF 1000 R0D HANGERSLWILL REQUIRE MODIFICATION, 100 PRE-RESTART AND 200 POST RESTART l

o NPK-4226M i l

4 t

. CRITERIA FOR DRYWELLLPLATFORM CLIP ~ ANGLES -(CSG-19)

STATEMFNT OF THE ISSUE o USE OF TEST RESULTS FOR QUALIFICATION OF DRYWELL PLATFORM CLIP ANGLES

' PROPOSED RESOLUTION

• TVA-WITH PRIOR NRC-AGREEMENT, MAY USE TESTS TO DEFINE STRUCTURAL BEHAVIOR e OPERABILITY CRITERIA USED FOR. ACCEPTANCE NPr'. '(.

_y 3 ,

h, DISTRIBUTION FOR MEETING

SUMMARY

DATED: March 22, 1989 Facility: Browns Ferry Nuclear Plant, Unit E*

-vDeWiEEfile NRC PDR Local'PDR Projects Reading

-ADSP Reading

-D. Crutchfield B. D. Liaw i - S. Black'

R. Pierson L

G. Gears

D. Moran M. Simms F. McCoy J. Rutberg D. Terao J. R. Fair T. M. Cheng E. Goodwin ACRS(10)

GPA/PA' GPA/CA (M. Callahan) (5)

S. Varga E. Jordan B. Grimes P. Gwynn' J. Scarborough G. Marcus T. Elsasser L. Norrholm C. Ader l- BFN Rdg. File

• cc: Licensee / Applicant & Service List

_- -___- e __-_--____- - _ _ - _ _ _